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Spent fuel recycling and conditioning topic of U.S.-Japan meeting
Officials with the Department of Energy’s Office of Environmental Management discussed spent nuclear fuel recycling and conditioning with counterparts from Japan during the 13th U.S.-Japan Technical Meeting of the Civil Nuclear Energy Research and Development Working Group, held recently in Santa Fe, N.M.
J. J. Koelling, G. E. Hansen, C. C. Byers
Nuclear Technology | Volume 35 | Number 3 | October 1977 | Pages 611-616
Technical Paper | Reactor Siting | doi.org/10.13182/NT77-A31870
Articles are hosted by Taylor and Francis Online.
The critical masses and fission and explosive energy releases of PuO2, PuO2-U2, UO2, and UO3 assemblies have been calculated. The parameters selected for the model are conservative. They were chosen after review of appropriate plants that have been and are proposed for construction in the future. The resulting data envelopes are intended to include any conceivable set of circumstances that could ultimately lead to a nuclear incident. All energy release analysis was performed for initial fission spikes only: recriticality mechanisms were not considered.